ML16253A126: Difference between revisions

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{{#Wiki_filter:1From:Dentel, Glenn Sent:Thursday, September 08, 2016 2:45 PM To:DR WILLIAM CORCORAN Cc:McKenzie, Kieta; Scott, Michael; Pelton, David
{{#Wiki_filter:1 From: Dentel, Glenn Sent: Thursday, September 08, 2016 2:45 PM To: DR WILLIAM CORCORAN Cc: McKenzie, Kieta; Scott, Michael; Pelton, David


==Subject:==
==Subject:==

Revision as of 06:06, 8 July 2018

G. Dentel E-ail to W. Corcoran Ucs Bolt Assessment of Operability
ML16253A126
Person / Time
Site: Indian Point  Entergy icon.png
Issue date: 09/08/2016
From: Dentel G T
Reactor Projects Branch 2
To: Corcoran W R
- No Known Affiliation
Dentel G T
References
2016 SST - 523
Download: ML16253A126 (1)


Text

1 From: Dentel, Glenn Sent: Thursday, September 08, 2016 2:45 PM To: DR WILLIAM CORCORAN Cc: McKenzie, Kieta; Scott, Michael; Pelton, David

Subject:

RE: Re: UCS bolt assessment of operability

Dear Dr. Corcoran:

As promised in my June 16 email response to you, I am writing to let you know the NRC has issued an inspection report on baffle-former bolting conditions at Indian Point Units 2 and 3. This inspection report can be found by using the NRC's publicly available web-based Agencywide Documents Access and Management System. To retrieve the document, enter the Acce ssion Number (ML16243A245) in the Document Properties field located in the Advanced Search tab at the following webpage: http://adams.nrc.gov/wba/. The NRC implemented significant, comprehensive inspection s after learning of the degraded baffle-former bolt issues at Indian Point. This included various baseline inspection samples to assess the issue at Unit 2, and the extent of the issue as it pertains to Unit 3. The inspections included reviews of Entergy's non-destructive examination techniques and results; observations of a portion of bolt replacement activities on-site; assessments of foreign material controls and loose parts analysis; and reviews of the design change package and evaluations associated with both the degraded and new, replacement baffle-former bolts. Enforcement action was taken for Entergy's failure to perform an operability evaluation on the baffle-former bolts associated with Unit 3. All of these inspections and other reviews are documented in the above mentioned report. In

summary, NRC inspectors reviewed Entergy's actions to address the baffle-former bolting issue and concluded there are no concerns pertaining to the safe operation of Units 2 and 3" Thank you for your concerns about the safe operations of the Indian Point nuclear plant. If you have any questions regarding this email or the inspection report, please contact me at (610) 337-5233.

Sincerely, Glenn Dentel, Chief Division of Reactor Projects Branch 2 NRC Region I